JPS5844240B2 - How to operate a boiling water nuclear power plant - Google Patents
How to operate a boiling water nuclear power plantInfo
- Publication number
- JPS5844240B2 JPS5844240B2 JP51080996A JP8099676A JPS5844240B2 JP S5844240 B2 JPS5844240 B2 JP S5844240B2 JP 51080996 A JP51080996 A JP 51080996A JP 8099676 A JP8099676 A JP 8099676A JP S5844240 B2 JPS5844240 B2 JP S5844240B2
- Authority
- JP
- Japan
- Prior art keywords
- boiling water
- reactor
- power plant
- nuclear power
- turbine
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Control Of Steam Boilers And Waste-Gas Boilers (AREA)
Description
【発明の詳細な説明】
本発明は沸騰水型原子炉の運転方法に係り、特に原子炉
の給水温度を制御して燃料の燃焼度を改善した沸騰水型
原子力発電所の運転方法に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method of operating a boiling water nuclear reactor, and more particularly to a method of operating a boiling water nuclear power plant that improves fuel burnup by controlling the reactor feed water temperature.
従来の沸騰水型原子炉の発電プラントは、原子炉への給
水をタービンからの抽気蒸気で給水加熱器を介して加熱
している。In a conventional boiling water reactor power plant, feed water to the reactor is heated with extracted steam from a turbine via a feed water heater.
しかし、給水加熱量は制御されていない。However, the amount of heating of the feed water is not controlled.
ところで、第1図に示す如く沸騰水型原子炉は、炉心熱
出力を一定にすると給水温度が高くなるにしたがって炉
心内のボイド率は増加する。By the way, as shown in FIG. 1, in a boiling water reactor, when the core thermal output is kept constant, the void ratio in the core increases as the feed water temperature increases.
これによって、水の中性子減速能は低下して熱中性子数
が減少する。This reduces the neutron moderating ability of water and reduces the number of thermal neutrons.
このため中性子実効増倍率は、第2図に示す如く給水温
度が高くなるにしたがって低下する。Therefore, the effective neutron multiplication factor decreases as the feed water temperature increases, as shown in FIG.
又、中性子の無限増倍率は第3図に示す如く燃焼度によ
って変化すると共にボイド率によっても変化する。Further, the infinite multiplication factor of neutrons changes depending on the burnup as shown in FIG. 3, and also changes depending on the void ratio.
すなわち、無限増倍率は燃焼度のある値でピーク点を有
し、左右どちらに移動しても低下する。That is, the infinite multiplication factor has a peak point at a certain value of burnup, and decreases regardless of whether it moves to the left or right.
又、無限増倍率は、ボイド率が小さい程大きくなる。Moreover, the infinite multiplication factor becomes larger as the void ratio becomes smaller.
更に、平均ボイド率が大きい程、燃焼度末期の中性子増
倍率は太きい。Furthermore, the larger the average void fraction, the larger the neutron multiplication factor at the end of burnup.
これは、Pu239 の生成がボイド率が大きい程大き
いからである。This is because the generation of Pu239 increases as the void ratio increases.
ところが、上記従来の原子力発電プラントは、前述の効
果を考慮せず、燃焼度の全期にわたってほぼ40%の平
均ボイド率(定格出力時)で運転している。However, the above-mentioned conventional nuclear power plant does not consider the above-mentioned effects and operates at an average void ratio (at rated output) of approximately 40% over the entire burnup period.
本発明は、上述の事情に鑑みてなされたもので、原子炉
のボイド率を、装荷された燃料を交換することなくして
運転する1期間中に変化させて1運転期間(1サイクル
)中の燃焼度を改善する沸騰水型原子力発電所の運転方
法を得ることを目的とする。The present invention was made in view of the above-mentioned circumstances, and the void ratio of a nuclear reactor is changed during one operating period (one cycle) without replacing the loaded fuel. The objective is to obtain an operating method for boiling water nuclear power plants that improves burnup.
すなわち、本発明の沸騰水型原子力発電所の運転方法は
、装荷された燃料を交換することなくして運転する期間
の前半はボイド率を高くし、後半になるにしたがってボ
イド率を下げていく運転方法である。In other words, the method of operating a boiling water nuclear power plant of the present invention is to increase the void rate during the first half of the period in which the loaded fuel is not replaced, and to reduce the void rate in the second half. It's a method.
以下図面を参照して本発明の一実施例を説明する。An embodiment of the present invention will be described below with reference to the drawings.
第4図に示す如く沸騰水型原子炉(以下単に原子炉と記
す)41は主蒸気ライン42を介してタービン43.4
4に接続されている。As shown in FIG. 4, a boiling water reactor (hereinafter simply referred to as a nuclear reactor) 41 is connected to a turbine 43.
Connected to 4.
タービン43.44はタンデム接続され、タービン43
で仕事をした蒸気は、接続ライン45を介してタービン
44に入り、これを駆動する。The turbines 43, 44 are connected in tandem, and the turbines 43, 44 are
The steam that has done work enters the turbine 44 via the connection line 45 and drives it.
タービン44には主復水器46が接続される。A main condenser 46 is connected to the turbine 44 .
主復水器46は、復水ポンプ47を介して第1の給水加
熱器48に接続される。The main condenser 46 is connected to a first feedwater heater 48 via a condensate pump 47 .
この給水加熱器48は、給水ポンプ49を介して第2の
給水加熱器50に接続される。This feedwater heater 48 is connected to a second feedwater heater 50 via a feedwater pump 49 .
この第2の給水加熱器50は、第3の給水加熱器51を
介して前記原子炉41へ接続される。This second feedwater heater 50 is connected to the nuclear reactor 41 via a third feedwater heater 51.
前記タービン43と前記第3の給水加熱器51とを結ぶ
抽気ライン52には、第3の可変絞り弁53が介設され
る。A third variable throttle valve 53 is interposed in a bleed line 52 connecting the turbine 43 and the third feedwater heater 51 .
又、前記第2の給水加熱器50と前記接続ライン45を
結ぶ抽気ライン54には、第2の可変絞り弁55が介設
される。Further, a second variable throttle valve 55 is interposed in the bleed line 54 connecting the second feed water heater 50 and the connection line 45.
更に、前記第1の給水加熱器4Bとタービン44を結ぶ
抽気ライン56には、第1の可変絞り弁57が介設され
ている。Furthermore, a first variable throttle valve 57 is interposed in the extraction line 56 connecting the first feed water heater 4B and the turbine 44.
次に運転方法を説明する。Next, the driving method will be explained.
先ず、1サイクル中の運転初期から中期にかけては、第
5図、第6図に示す如く第1〜第3の可変絞り弁57,
55゜53を全開にして給水温度を高めて運転する。First, from the beginning to the middle of one cycle of operation, the first to third variable throttle valves 57,
55°53 is fully opened and the water supply temperature is raised.
すなわち、運転初期はボイド率を高めて中性子スペクト
ルを硬化させて運転する。That is, in the initial stage of operation, the void ratio is increased to harden the neutron spectrum.
このためU238の中性子共鳴吸収が増加して、Pu2
39 への転換比が増加し燃焼度が改善される。Therefore, the neutron resonance absorption of U238 increases and Pu2
The conversion ratio to 39% is increased and the burnup is improved.
運転が継続されて燃焼度末期に近づいたなら第1〜第3
の可変絞り弁57,55.53を絞って給水温度を下げ
ボイド率を低くして運転する。If the operation continues and the burnup approaches the end, the first to third
The variable throttle valves 57, 55, and 53 are throttled to lower the feed water temperature and lower the void rate during operation.
このため軟化した中性子スペクトルによってPu239
が核反応に寄与して燃焼度を増すことができる。Therefore, due to the softened neutron spectrum, Pu239
can contribute to nuclear reactions and increase burnup.
この可変絞り弁の操作は、第5図、第6図に示す如く急
激に絞り込んでも良いが段階的に数回に分けて絞り込む
様にすると炉心への影響をより改善することができる。The operation of the variable throttle valve may be performed by rapidly reducing the throttle as shown in FIGS. 5 and 6, but if the variable throttle valve is operated in several stages, the influence on the reactor core can be further improved.
これは、第7図に示す如く可変絞り弁53,55゜57
の開閉操作を、炉心へ挿入されている制御棒40の挿入
状態をプロセスボンピユータ71で制御することによっ
て行なえる。This is the variable throttle valve 53,55°57 as shown in FIG.
The opening and closing operations can be performed by controlling the insertion state of the control rod 40 inserted into the reactor core using the process bombimeter 71.
すなわち、制御棒40の挿入密度CRDがある値CRD
oよりも低くなったら可変絞り弁53,55.57を絞
り込んで給水温度を下げる。That is, the insertion density CRD of the control rod 40 is a certain value CRD
When the temperature becomes lower than o, the variable throttle valves 53, 55, and 57 are throttled down to lower the water supply temperature.
これを、第8図のフローチャートを利用して説明すれば
、炉心1の制御棒密度を2で計算し、その結果CHDを
比較器3のCRDoと比較し、CHD<CRDoの関係
にあれば可変絞り弁53,55.57を絞り込む。To explain this using the flowchart in Figure 8, the control rod density of the core 1 is calculated by 2, the resulting CHD is compared with the CRDo of the comparator 3, and if the relationship CHD<CRDo is satisfied, the control rod density can be changed. Squeeze the throttle valves 53, 55, and 57.
反対にCHD>CRDoの関係であれば可変絞り弁53
.55.57を開く。On the other hand, if the relationship is CHD>CRDo, the variable throttle valve 53
.. Open 55.57.
尚、給水加熱器へ流入する加熱蒸気は、原子炉から直に
主蒸気を抽出しても良い。Note that main steam may be extracted directly from the reactor as the heating steam flowing into the feedwater heater.
以上説明のように本発明の沸騰水型原子力発電所の運転
方法は、給水温度を制御して運転するためU238から
Pu239への転換比が向上して燃焼度を改善できる。As described above, the boiling water nuclear power plant operating method of the present invention operates by controlling the temperature of the feed water, so that the conversion ratio from U238 to Pu239 can be improved and the burnup can be improved.
又、これにより制御棒をより多く引抜くことが可能とな
り出力分布の平坦化(炉心特性の向上)に役立つ。This also makes it possible to withdraw more control rods, which helps flatten the power distribution (improve core characteristics).
更に制御棒と同じように反応度の制御が行なえる制御棒
の制御能力を小さくすることができる。Furthermore, the control capability of the control rod, which can control reactivity in the same way as the control rod, can be reduced.
第1図は給水温度とボイド率の関係を示すグラフ、第2
図は給水温度と実効増倍率の関係を示すグラフ、第3図
は燃焼度と無限増倍率の関係をボイド率を基に示すグラ
フ、第4図は本発明の沸騰水型原子力発電所の運転方法
を説明するための系統図、第5図は1サイクル中の弁の
開度の状態を示すグラフ、第6図は1サイクル中の給水
温度を示すグラフ、第7図は本発明の他の実施例を示す
プロセス系統図、第8図は第7図の運転方法を示すフロ
ーチャート図である。
41・・・・・・原子炉、43,44・・・・・・ター
ビン、48.50.51・・・・・・給水加熱器、53
,55゜57・・・・・・可変絞り弁。Figure 1 is a graph showing the relationship between feed water temperature and void ratio.
Figure 3 is a graph showing the relationship between feed water temperature and effective multiplication factor, Figure 3 is a graph showing the relationship between burnup and infinite multiplication factor based on void ratio, and Figure 4 is the operation of the boiling water nuclear power plant of the present invention. A system diagram for explaining the method, FIG. 5 is a graph showing the opening degree of the valve during one cycle, FIG. 6 is a graph showing the feed water temperature during one cycle, and FIG. 7 is a graph showing another method of the present invention. FIG. 8 is a flowchart showing the operating method of FIG. 7, which is a process system diagram showing an embodiment. 41...Nuclear reactor, 43,44...Turbine, 48.50.51...Feed water heater, 53
, 55° 57... Variable throttle valve.
Claims (1)
駆動されるタービンと、このタービンから出てきた蒸気
を復水にする復水器と、この復水器からの復水を前記タ
ービン又は原子炉から抽出した蒸気で加熱する給水加熱
器と、この給水加熱器と前記タービン又は原子炉を結ぶ
抽出ラインに介設された可変絞り弁とから構成された沸
騰水型原子力発電所において、前記可変絞り弁を運転開
始当初は開にしておき、運転が進行するにしたがって絞
り込んでいくことを特徴とする沸騰水型原子力発電所の
運転方法。1 Boiling water reactor and the steam generated by this reactor,
A turbine to be driven, a condenser that condenses the steam coming out of the turbine, a feed water heater that heats the condensate from the condenser with steam extracted from the turbine or the reactor, and In a boiling water nuclear power plant comprising a feedwater heater and a variable throttle valve installed in an extraction line connecting the turbine or the reactor, the variable throttle valve is left open at the beginning of operation and the operation is continued. A boiling water nuclear power plant operating method characterized by narrowing down as the process progresses.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP51080996A JPS5844240B2 (en) | 1976-07-09 | 1976-07-09 | How to operate a boiling water nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP51080996A JPS5844240B2 (en) | 1976-07-09 | 1976-07-09 | How to operate a boiling water nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS538495A JPS538495A (en) | 1978-01-25 |
| JPS5844240B2 true JPS5844240B2 (en) | 1983-10-01 |
Family
ID=13734090
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP51080996A Expired JPS5844240B2 (en) | 1976-07-09 | 1976-07-09 | How to operate a boiling water nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5844240B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60174649U (en) * | 1984-04-27 | 1985-11-19 | 愛知機械工業株式会社 | box |
Families Citing this family (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2521256B2 (en) * | 1986-03-05 | 1996-08-07 | 株式会社日立製作所 | Natural circulation boiling water reactor control method |
| JP2007232500A (en) * | 2006-02-28 | 2007-09-13 | Hitachi Ltd | Operation method of nuclear reactor and nuclear power plant |
| JP4982270B2 (en) * | 2006-06-27 | 2012-07-25 | 日立Geニュークリア・エナジー株式会社 | Reactor operating method and nuclear power plant |
| JP5502267B2 (en) * | 2007-08-02 | 2014-05-28 | 株式会社東芝 | Reactor operation method |
| JP5449716B2 (en) * | 2008-07-31 | 2014-03-19 | 株式会社東芝 | Boiling water reactor |
| JP5452513B2 (en) * | 2011-01-27 | 2014-03-26 | 日立Geニュークリア・エナジー株式会社 | Reactor operation method |
| JP7508389B2 (en) * | 2021-02-25 | 2024-07-01 | 日立Geニュークリア・エナジー株式会社 | Nuclear power plant output control device and output control method |
-
1976
- 1976-07-09 JP JP51080996A patent/JPS5844240B2/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60174649U (en) * | 1984-04-27 | 1985-11-19 | 愛知機械工業株式会社 | box |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS538495A (en) | 1978-01-25 |
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